ORAU TEAM

Dose Reconstruction

Project for NIOSH

Oak Ridge Associated Universities I Dade Moeller & Associates I MJW Corporation

Page 1 of 30

Document Title:

Internal Dosimetry Coworker Data for the Mound 

Site

Document Number: ORAUT-OTIB-0061

Revision: 00

Effective Date: 06/22/2007

Type of Document OTIB

Supersedes: None

Subject Expert(s): Joseph C. Lochamy and Mike Mahathy

Site Expert(s): Thomas R. LaBone

Approval: Signature on File Approval Date: 06/04/2007

Clark B. Barton, Document Owner

Concurrence: Signature on File Concurrence Date: 06/01/2007

John M. Byrne, Task 3 Manager

Concurrence: Signature on File Concurrence Date: 06/01/2007

Edward F. Maher, Task 5 Manager

Concurrence: Signature on File Concurrence Date: 06/12/2007

Kate Kimpan, Project Director

Approval: Brant A. Ulsh Signature on File for Approval Date: 06/22/2007

James W. Neton, Associate Director for Science

 New Total Rewrite Revision Page Change

FOR DOCUMENTS MARKED AS A TOTAL REWRITE, REVISION, OR PAGE CHANGE, REPLACE THE PRIOR 

REVISION AND DISCARD / DESTROY ALL COPIES OF THE PRIOR REVISION.
Document No. ORAUT-OTIB-0061 Revision No. 00 Effective Date: 06/22/2007 Page 2 of 30

PUBLICATION RECORD

EFFECTIVE 

DATE

REVISION 

NUMBER DESCRIPTION

06/22/2007 00 Approved new technical information bulletin for assigning Mound 

internal doses based on coworker bioassay data. Incorporates 

formal internal and NIOSH review comments. There is no change to 

the assigned dose and no PER is required. Training required: As 

determined by the Task Manager. Initiated by Clark B. Barton.
Document No. ORAUT-OTIB-0061 Revision No. 00 Effective Date: 06/22/2007 Page 3 of 30

TABLE OF CONTENTS

SECTION TITLE

Acronyms and Abbreviations ...............................................................................................................

PAGE

6

1.0 Introduction ..............................................................................................................................7

2.0 Purpose ...................................................................................................................................7

3.0 Data Overview .........................................................................................................................8

3.1 Bioassay Data Selection...............................................................................................8

3.1.1 Polonium Urinalysis Data .................................................................................. 8

3.1.2 Plutonium Urinalysis Data .................................................................................8

3.2 Analysis........................................................................................................................8

3.2.1 Polonium Bioassay Analysis ............................................................................. 8

3.2.2 Plutonium Bioassay Analysis ............................................................................ 9

4.0 Intake Modeling........................................................................................................................9

4.1 Assumptions.................................................................................................................9

4.1.1 Polonium Assumptions......................................................................................9

4.1.2 Plutonium Assumptions.....................................................................................9

4.2 Bioassay Fitting ..........................................................................................................10

4.2.1 Polonium Fitting .............................................................................................. 10

4.2.2 Plutonium Fitting ............................................................................................. 10

4.3 Material Types............................................................................................................10

4.3.1 Polonium......................................................................................................... 10

4.3.2 Plutonium........................................................................................................ 10

5.0 Assigning Intakes and Doses ................................................................................................. 11

5.1 Intake Rate Summary................................................................................................. 11

5.1.1 Polonium......................................................................................................... 11

5.1.2 Plutonium........................................................................................................ 12

5.2 Dose Assignment .......................................................................................................13

6.0 Attributions and Annotations .................................................................................................. 13

References ........................................................................................................................................16

ATTACHMENT A, COWORKER DATA TABLES............................................................................... 17

ATTACHMENT B, COWORKER DATA FIGURES ............................................................................ 21
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LIST OF TABLES

TABLE TITLE

5-1 Derived polonium intakes, 1944 to 1973 ................................................................................

PAGE

12

5-2 Derived plutonium intake rates, 1956 to 1990 ........................................................................ 12

5-3 Dose calculations for WGPU or HSPU intakes....................................................................... 13

A-1 50th- and 84th-percentile urinary excretion rates of 210Po, 1944 to 1957................................ 17

A-2 50th- and 84th-percentile urinary excretion rates of 210Po, 1958 to 1973................................ 18

A-3 Type M 210Po intake rates and dates ...................................................................................... 18

A-4 Type F 210Po intake rates and dates....................................................................................... 18

A-5 50th- and 84th-percentile urinary excretion rates of total plutonium, 1956 to 1975 ................. 19

A-6 50th- and 84th-percentile urinary excretion rates of total plutonium, 1975 to 1990 ................. 20

A-7 Type M plutonium intake rates and dates............................................................................... 20

A-8 Type S plutonium intake rates and dates ............................................................................... 20

LIST OF FIGURES

FIGURE TITLE

B-1 Predicted and observed 50th-percentile urinary excretion assuming inhalation intakes of 

type M 210Po...........................................................................................................................

PAGE

21

B-2 Predicted and observed 84th-percentile urinary excretion assuming inhalation intakes of 

type M 210Po...........................................................................................................................21

B-3 Predicted and observed 50th-percentile urinary excretion assuming inhalation intakes of 

type F 210Po............................................................................................................................22

B-4 Predicted and observed 84th-percentile urinary excretion assuming inhalation intakes of 

type F 210Po............................................................................................................................22

B-5 Predicted and observed 50th-percentile urinary excretion assuming inhalation intakes of 

type M plutonium, 1956 to 1957 ............................................................................................. 23

B-6 Predicted and observed 50th-percentile urinary excretion assuming inhalation intakes of 

type M plutonium, 1958 to 1960 ............................................................................................ 23

B-7 Predicted and observed 50th-percentile urinary excretion assuming inhalation intakes of 

type M plutonium, 1961 to 1969 ............................................................................................. 24

B-8 Predicted and observed 50th-percentile urinary excretion assuming inhalation intakes of 

type M plutonium, 1970 to 1984 ............................................................................................. 24

B-9 Predicted and observed 50th-percentile urinary excretion assuming inhalation intakes of 

type M plutonium, 1985 to 1990 ............................................................................................. 25

B-10 Predicted and observed 50th-percentile urinary excretion assuming inhalation intakes of 

type M plutonium, 1956 to 1990 ............................................................................................. 25

B-11 Predicted and observed 84th-percentile urinary excretion assuming inhalation intakes of 

type M plutonium, 1956 to 1960 ............................................................................................. 26

B-12 Predicted and observed 84th-percentile urinary excretion assuming inhalation intakes of 

type M plutonium, 1961 to 1967 ............................................................................................. 26

B-13 Predicted and observed 84th-percentile urinary excretion assuming inhalation intakes of 

type M plutonium, 1968 to 1969 ............................................................................................. 27

B-14 Predicted and observed 84th-percentile urinary excretion assuming inhalation intakes of 

type M plutonium, 1970 to 1977 ............................................................................................. 27
Document No. ORAUT-OTIB-0061 Revision No. 00 Effective Date: 06/22/2007 Page 5 of 30

B-15 Predicted and observed 84th-percentile urinary excretion assuming inhalation intakes of 

type M plutonium, 1978 to 1984 ............................................................................................. 28

B-16 Predicted and observed 84th-percentile urinary excretion assuming inhalation intakes of 

type M plutonium, 1985 to 1990 ............................................................................................. 28

B-17 Predicted and observed 84th-percentile urinary excretion assuming inhalation intakes of 

type M plutonium, 1956 to 1990 ............................................................................................. 29

B-18 Predicted and observed 50th-percentile urinary excretion assuming a single chronic 

inhalation intake of type S plutonium, 1956 to 1990 ............................................................... 29

B-19 Predicted and observed 84th-percentile urinary excretion assuming a single chronic 

inhalation intake of type S plutonium, 1956 to 1990 ............................................................... 30
Document No. ORAUT-OTIB-0061 Revision No. 00 Effective Date: 06/22/2007 Page 6 of 30

ACRONYMS AND ABBREVIATIONS

AMAD activity median aerodynamic diameter

Bq becquerel

d day

DOE U.S. Department of Energy

DTPA diethylene triamine pentaacetic acid

EEOICPA Energy Employees Occupational Illness Compensation Program Act

GI gastrointestinal

GSD geometric standard deviation

hr hour

HSPU heat-source plutonium

IMBA Integrated Modules for Bioassay Analysis

IREP Interactive RadioEpidemiological Program

m meter

mL milliliter

NIOSH National Institute for Occupational Safety and Health

ORAU Oak Ridge Associated Universities

pCi picocurie

PER Program Evaluation Report

POC probability of causation

TIB technical information bulletin

U.S.C. United States Code

WGPU weapons-grade plutonium

μg microgram

μm micrometer

§ section or sections
Document No. ORAUT-OTIB-0061 Revision No. 00 Effective Date: 06/22/2007 Page 7 of 30

1.0

Technical information bulletins (TIBs) are not official determinations made by the National Institute for 

Occupational Safety and Health (NIOSH) but are rather general working documents that provide 

historical background information and guidance to assist in the preparation of dose reconstructions at 

particular sites or categories of sites. They will be revised if additional relevant information is 

obtained. TIBs may be used to assist NIOSH staff in the completion of individual dose 

reconstructions.

INTRODUCTION

In this document the word “facility” is used as a general term for an area, building, or group of 

buildings that served a specific purpose at a site. It does not necessarily connote an “atomic weapons 

employer facility” or a “Department of Energy [DOE] facility” as defined in the Energy Employees 

Occupational Illness Compensation Program Act of 2000 [42 U.S.C. § 7384l(5) and (12)].

Analysis of Coworker Bioassay Data for Internal Dose Assignment (ORAUT 2005) describes the

general process that is used to analyze bioassay data for assigning doses to individuals based on 

coworker results. Coworker Data Exposure Profile Development (ORAUT 2004a) describes the 

approach and processes to be used to develop reasonable exposure profiles based on available 

dosimetric information for workers at DOE sites.

Bioassay results were obtained through the PORECON (Polonium Reconstruction) and PURECON 

(Plutonium Reconstruction) databases that were created at the Mound Laboratory from logbooks and 

other original hard-copy records. Based on a spot check, this data set coincides well with original 

Mound paper records. It is appropriate for use only at Mound. Furthermore, the databases are 

representative of worker bioassay results at Mound during a substantial part of the operating history at 

this site. 

The database results were labeled with units that varied among the radionuclides, analysis 

techniques, and measurement periods. These units were assembled into a common format to 

expedite the statistical analysis. The specific units for each radionuclide are provided in the 

appropriate sections of this document.

A statistical analysis of the data was performed as specified in ORAUT (2005) and it’s implementing 

procedure, Generating Summary Statistics for Coworker Bioassay Data (ORAUT 2006). The results 

were entered in the Integrated Modules for Bioassay Analysis (IMBA) computer software to obtain 

intake rates for assigning dose distributions.

2.0

Some employees at DOE sites might not have been monitored for potential intakes of radioactive 

material. For other employees the records of such monitoring might be incomplete or unavailable. In 

such cases, data from monitored coworkers can be used to estimate an individual’s potential intake of 

radioactive material and the resulting internal dose. The purpose of this TIB is to provide monitored 

coworker information for calculating and assigning occupational internal doses to employees at 

Mound whose job titles, facility assignments, and other case-specific information indicate that they 

have the potential for unmonitored intakes of 210Po or plutonium.

PURPOSE

Attributions and annotations, indicated by bracketed callouts used to identify the source, justification, 

or clarification of the associated information, are presented in § 6.0.
Document No. ORAUT-OTIB-0061 Revision No. 00 Effective Date: 06/22/2007 Page 8 of 30

3.0

This section provides information on the general selection characteristics of the data and the methods 

of analysis. Plutonium and 210Po are the radionuclides of interest, and significant numbers of 

monitoring records exist for them. More detailed radionuclide-specific information for these two 

nuclides is provided in Section 4.0.

DATA OVERVIEW

3.1 BIOASSAY DATA SELECTION

3.1.1

The urine bioassay data were extracted from the verified PORECON_FINAL_COPY database, 

“dbo_SAMPLES” table, “BQ_DAY” field. By verified, it is meant that the original PORECON database 

was created by Mound from information recorded on cards, as well as from a review of the original 

chemistry logbooks from which the cards were created. Data entry clerks entered the data using 

double-entry methods. Following this task, data entry was reviewed by health physicists. Samples 

with PROBLEM_FLG = “R” or BQ_DAY = blank were not included in the statistical analysis [1]. 

Polonium Urinalysis Data

3.1.2

Urine bioassay data (SAMPLE_TYPE = U) and the analysis date (Date = SAMPLE_DATE) were 

extracted from the PURECON table of the verified PURECON_MERGED database. By verified, it is 

meant that the original PURECON database used for this analysis was created by Mound from 

logbooks and other original hard-copy records. Results with any of the following identifiers were 

excluded: PROBLEM_FLG = nonblank, DTPA = nonblank, LNAME = QC, or Result field 

(PICOC_PU238 or PICOC_PU239) = blank. There was a comment field associated with each result 

and, in most cases with a PROBLEM_FLG = nonblank, the comment indicated the reason for the flag. 

These included samples with low recovery, no tracer added, samples lost in process, insufficient 

volume for analysis, samples with no result, samples following diethylene triamine pentaacetic acid 

(DTPA) administration (chelation therapy), and samples that were analyzed for nuclides other than 

plutonium. Note that 1,413 of 58,893 results were marked with a problem flag. In the first quarter of 

1983, 26 sample results were excluded because the comment field indicated that 239Pu was added to 

the sample [2]. 

Plutonium Urinalysis Data

3.2 ANALYSIS

3.2.1

Data were analyzed by calendar quarter from July 1944 through the end of 1970 and by year from 

1971 through part of 1973. Results of samples reported with dates in 1940 and 1941 were not used 

because the site was not yet operational. Spot samples were collected for analysis; 50- or 100-mL 

aliquots were analyzed, and the results were typically reported in units of counts per minute or 

disintegrations per minute. Values in the “BQ_DAY” field originally had been calculated and entered 

into the database assuming a counting efficiency of 50% and a chemical recovery of 85%. They were 

normalized to a 24-hr sample assuming an excretion rate of 1,400 mL/d. Before the statistical 

analysis was run, the results from 1944 through 1963 were multiplied by a factor of 8.5 according to 

the guidance in Technical Basis Document for the Mound Site – Occupational Internal Dosimetry

(ORAUT 2004b), which specifies a recovery efficiency of 10% (instead of 85%) for this time frame. A 

factor of 1.35 was applied to results from 1964 through 1973, again according to ORAUT (2004b), 

which specifies a recovery efficiency of 63% (instead of 85%) for this time frame. 

Polonium Bioassay Analysis
Document No. ORAUT-OTIB-0061 Revision No. 00 Effective Date: 06/22/2007 Page 9 of 30

A lognormal distribution was assumed for the urinary excretion data, and the 50th- and 84th-percentile 

excretion rates were calculated using the method prescribed in ORAUT (2006). These excretion rates 

are given in Tables A-1 and A-2. Bioassay data collected over a specified period were analyzed to 

determine the 50th- and 84th-percentile excretion rates for that period. The effective bioassay dates 

are the midpoints of the periods, and they were used in IMBA to calculate the intake rates.

3.2.2

Data were analyzed by year from 1956 through the end of 1961 and by calendar quarter from 1962 

through 1990. The results from 1954 through 1960 were multiplied by a factor of 8.5, as specified in 

ORAUT (2004b). Analyses before June 1, 1981, which measured total plutonium alpha, were 

reported in the “PICOC_PU238” field, whereas later results, which were isotopic plutonium, were 

reported in the fields “PICOC_PU238” and “PICOC_PU239.” The 238Pu and 239/240Pu results for each 

sample analyzed after June 1, 1981, were summed to create a total plutonium result for these 

samples. 

Plutonium Bioassay Analysis

A lognormal distribution was assumed for the urinary excretion data, and the 50th- and 84th-percentile

excretion rates were calculated using the method in ORAUT (2006). These excretion rates are given 

in Tables A-5 and A-6. Bioassay data collected over a specified period were analyzed to determine 

the 50th- and 84th-percentile excretion rates for that period. The effective bioassay dates are the 

midpoints of the periods and they are to be used in IMBA to calculate the intake rates.

4.0

This section discusses intake modeling assumptions, fitting, and materials (polonium and plutonium).

INTAKE MODELING

4.1 ASSUMPTIONS

4.1.1

Each urinary excretion rate used in the intake calculations was assumed to be normally distributed. A 

uniform absolute error of 1 was applied to all results, which thus assigned the same weight to each 

result [4]. IMBA requires results in units of activity per day; therefore, all urinalysis results were 

normalized, as needed, to 24-hr samples using 1,400 mL, which is the volume of urine excreted by 

Reference Man in a 24-hr period [3]. 

Polonium Assumptions 

The excretion data were modeled with IMBA for multiple chronic intakes of type F or type M 210Po. 

Examination of excretion results for polonium indicated that relatively chronic exposures appear to 

have been likely at the start of the polonium program. Therefore, a chronic exposure pattern was 

assumed throughout the program because it also approximates a series of acute intakes with 

unknown intake dates. Intakes were assumed to be via inhalation with a default breathing rate of 

1.2 m3

/hr and a 5-μm activity median aerodynamic diameter (AMAD) particle size distribution [4]. 

4.1.2

All urinary excretion rates were modeled as normally distributed 24-hr urine samples having a uniform 

absolute error of 1, which thus assigned the same weight to each urinary excretion rate. The 

excretion data were modeled with IMBA for multiple chronic intakes of type M or a single chronic 

intake of type S plutonium. While it is unlikely that workers at Mound were chronically exposed to 

plutonium, this approach approximates a series of acute intakes with unknown intake dates. Intakes 

Plutonium Assumptions 
Document No. ORAUT-OTIB-0061 Revision No. 00 Effective Date: 06/22/2007 Page 10 of 30

were assumed to be via inhalation with a default breathing rate of 1.2 m3/hr and a 5-μm AMAD 

particle size distribution [5]. 

4.2 BIOASSAY FITTING

4.2.1

The excretion data were modeled with IMBA for multiple chronic intakes of type F or type M 210Po. 

Polonium data from 1944 through 1973 were fit as a series of chronic intakes. 

Polonium Fitting

The intake assumptions were based on patterns that were observed in the bioassay data. Periods 

with constant chronic intake rates were chosen by selecting periods during which the bioassay results 

were similar. A new chronic intake period was started if the data indicated a significant sustained 

change in the bioassay results. By this method, the period from 1944 through 1973 was divided into 

multiple chronic intake periods [6]. 

4.2.2

The excretion data were modeled with IMBA for multiple chronic intakes of type M or a single chronic 

intake of type S plutonium. Plutonium data from 1956 through 1990 were fit as a series of chronic 

intakes.

Plutonium Fitting 

The intake assumptions were based on patterns that were observed in the bioassay data. Periods 

with constant chronic intake rates were chosen by selecting periods during which the bioassay results 

were similar. A new chronic intake period was started if the data indicated a significant sustained 

change in the bioassay results. By this method, the period from 1956 through 1990 was divided into 

multiple chronic intake periods for type M plutonium. For type S plutonium, however, a single intake 

period from 1956 to 1990 was used [7]. 

4.3 MATERIAL TYPES

ORAUT (2004b) discusses Mound internal dosimetry data including guidance for the appropriate use 

of that information. According to that document, workers at Mound had the potential to receive 

intakes of polonium and plutonium.

4.3.1

Excretion data for the 50th- and 84th-percentile values of 210Po for 1944 through 1957 are shown in 

Table A-1. Excretion data for the 50th- and 84th-percentile values of 210Po for 1958 through 1973 are 

shown in Table A-2. Note that in Table A-2 the third quarter of 1970 was omitted because of poor 

statistics [8]. The solid lines in Figures B-1 and B-2 show the individual fits to the 50th- and 84thpercentile excretion rates, respectively, for type M 210Po material. The solid lines in Figures B-3 and 

B-4 show the individual fits to the 50th- and 84th-percentile excretion rates, respectively, for type F 

210Po material [9]. 

Polonium

4.3.2

Because plutonium of either type S or M has a very long half-life and the material is retained in the 

body for long periods, excretion results are not independent. For example, an intake in the early 

1950s could contribute to urinary excretion in the 1980s and later. To avoid potential underestimation 

of intakes for people who worked for relatively short periods, each type M intake period was fit 

Plutonium
Document No. ORAUT-OTIB-0061 Revision No. 00 Effective Date: 06/22/2007 Page 11 of 30

independently using only the bioassay results from that intake period. This fitting method will result in 

a best estimate of dose if the person worked in only one period and a potential overestimate if an 

individual worked in multiple periods. For type S plutonium, only one intake period, based on the 

latest and lowest excretion point, was used to create an underestimate for employment during any 

period [10]. 

Plutonium urinalysis results were analyzed with IMBA using type M and S materials to derive intake 

rates for 1956 to 1990. Type M intakes should be applied to all systemic organs. Type S must be 

considered for nonsystemic [i.e., lung and gastrointestinal (GI) tract] cancers [11]. 

Plutonium type M: The solid lines in Figures B-5 to B-10 show the individual fits to the 50thpercentile excretion rates for type M materials. The solid lines in Figures B-11 to B-17 show the 

individual fits to the 84th-percentile excretion rates for type M materials. The same intake periods

were not applied for both percentiles because the values followed different patterns [12]. 

Plutonium type S: Because type S plutonium clears more slowly from the lungs than types M and F, 

the plutonium exposure was fit as a single chronic intake from 1956 through 1990. This period was 

used because the measurements were relatively consistent; in addition, as the most recent 

measurements, they had the lowest minimum detectable activity and, therefore, were presumably the 

most accurate. The solid lines in Figures B-18 and B-19 show the individual fits to the 50th- and 84thpercentile excretion rates, respectively, for type S materials [13]. 

The type S intake rate can be used only as an underestimate

5.0

. If an overestimate or best estimate is 

needed for type S material, an individualized fit to the bioassay data for the specific work period of the 

energy employee being evaluated must be performed. Tables A-5 and A-6 provide the bioassay data 

for performing the individualized fit [14]. 

This section describes the derived intake rates and provides guidance for assigning doses.

ASSIGNING INTAKES AND DOSES

5.1 INTAKE RATE SUMMARY

5.1.1

Five intake periods were fit to the derived 50th- and 84th-percentile polonium excretion data. 

Because many of the geometric standard deviations (GSDs) were relatively similar, they were 

combined and the largest value within a given time frame was assigned for simplicity [15]. 

Polonium

The intake rates, GSDs, and periods in which they are applicable are given in Table A-3 for type M 

210Po and Table A-4 for type F 210Po. In most cases, doses for individuals potentially exposed

routinely are calculated from the 50th-percentile intake rates by assuming the solubility type that 

results in the largest probability of causation (POC)1

. Table 5-1 summarizes the derived polonium 

intake rates that produced the data-fitting results in Attachment B. Note that the results in Table 5-1 

are in becquerels

 

1. 1 The U.S. Department of Labor is responsible under EEOICPA for determining the POC.

per day, because the original data were recorded as such [16]. If pCi/day are 

preferred, multiply the Bq/d values by 27.
Document No. ORAUT-OTIB-0061 Revision No. 00 Effective Date: 06/22/2007 Page 12 of 30

Table 5-1. Derived polonium intakes, 1944 to 1973. 

Period

Type F material Type M material

50th percentile

(Bq/d) GSD

50th percentile

(Bq/d) GSD

07/1944–03/1946 1,189.5 3.89 4,097.6 3.9

04/1946–03/1949 254.96 5.56 800.19 5.8

04/1949–03/1960 12.192 7.99 39.851 8.0

04/1960–03/1965 2.0696 6.70 5.7883 6.2

04/1965–12/1973 0.10303 8.88 0.34853 8.8

5.1.2 

Seven intake periods were fit to the derived 50th- and 84th-percentile plutonium excretion data for 

type M material. One intake period was fit to the derived 50th- and 84th-percentile plutonium 

excretion data for type S material. If the GSD was less than 3, the value was set to 3 to account for 

biological variation when determining dose. Because of the interdependence among the bioassay 

results, it is not possible to fit type S plutonium to the data in a manner that would be representative of 

all individuals for all periods. Therefore, only a minimizing intake has been calculated for type S 

plutonium. 

Plutonium

Type M plutonium should be applied for all systemic organs. Type S plutonium should be 

applied for all nonsystemic (respiratory and GI tract) organs [17]

The intake rates, GSDs, and applicable periods are given in Table A-7 for type M plutonium and 

Table A-8 for type S plutonium. In most cases, doses for individuals potentially exposed routinely are 

calculated from the 50th-percentile intake rates by assuming the solubility type that results in the 

largest POC

. 

2

. Table 5-2 summarizes the derived plutonium intake rates that produced the data-fitting 

results in Attachment B. Note that the results in Table 5-2 are in picocuries

Table 5-2. Derived plutonium intake rates, 1956 to 1990. 

per day, because the 

original data were recorded as such [18]. If Bq/day are preferred, divide the pCi/d values by 27.

Period

50th percentile

(pCi/d) GSD

Type M material

1956–1957 750.98 3.00a

1958–1960 436.49 3.00a

1961–1967 12.141 5.42

1968–1969 12.141 11.69

1970–1977 2.2361 9.14

1978–1984 2.2361 5.82

1985–1990 0.59706 8.16

Type S material (underestimate)

1956–1990 0.54041 3.89

a. Actual GSD <3. Adjusted to 3 for dose calculations.

For nonsystemic (respiratory and GI tract) organs

1. Run the type M intakes. If this action does not result in a POC >50%, then

, dose reconstructors should follow these steps: 

2. Run the minimizing type S intake. If this action still does not yield a POC >50%, then 

 

2. 2 The U.S. Department of Labor is responsible under EEOICPA for determining the POC.
Document No. ORAUT-OTIB-0061 Revision No. 00 Effective Date: 06/22/2007 Page 13 of 30

3. Manually fit the coworker bioassay data for the time frame of interest for the employee, using 

the assumption of type S material.

Standard fitting techniques should be used to fit the plutonium urinalysis from the employee’s work 

period in Tables A-5 and A-6. Acute or chronic intakes can be assigned depending on the patterns in 

the data. The 50th-percentile intakes are used to assign the intake, and the 84th-percentile intakes 

are used to determine the GSD for each intake (GSD = 84th percentile/50th percentile). For input into 

the Interactive RadioEpidemiological Program (IREP), the dose from each intake must be determined 

separately [19]. 

5.2 DOSE ASSIGNMENT

For most cases, individual doses are calculated from the 50th-percentile intake rates. Dose 

reconstructors should select the material type that is the most favorable to claimants.

The lognormal distribution is selected in IREP, with the calculated dose entered as Parameter 1 and 

the associated GSD as Parameter 2. The GSD is associated with the intake, so it is applied to all 

annual doses determined from the intake period.

To calculate doses from plutonium, the intakes of “total Pu” should be classified as either weaponsgrade plutonium (WGPU) or heat-source plutonium (HSPU) using the established protocol for Mound. 

HSPU is assumed to be 100% 238Pu by activity, but determining the isotopic mix of WGPU is more 

complex. Table 5-3 lists three WGPU mixes aged 1, 3.2, and 10 years. These values are taken from 

the technical basis document (ORAUT 2004b). If the age of the isotopic mix is not known, the 10-yr 

aged material should be selected to be favorable to claimants regarding the in-growth of 241Am from 

241Pu. [20] 

Table 5-3. Dose calculations for WGPU intakes. 

Material age

(yr)

Percentage of alpha activity

Beta activity

(times APu-239/240)

Pu-239/240 Pu-238 Am-241 Pu-241

1 92.9 6.6 0.55 4.8

3.2 91.6 6.4 2.0 4.3

10 88.4 6.0 5.6 3.1

6.0

Where appropriate in this document, bracketed callouts have been inserted to indicate information, 

conclusions, and recommendations provided to assist in worker dose reconstruction. These callouts 

are listed here in this Attributions and Annotations section, with information to identify the source and 

justification for each associated item. Conventional references, which are provided in the next section 

of this document, link data, quotations, and other information to documents available for review on the 

Project Site Research Database.

ATTRIBUTIONS AND ANNOTATIONS

Thomas LaBone serves as a Site Expert for this document. As such, he is responsible for advising on 

site-specific issues and incidents as necessary and ensures the completeness and accuracy of the 

document. Because of his prior work experience for the site, he possesses, or is aware of information 

that is relevant for reconstructing radiation doses experienced by claimants who worked at the site. In 

all cases where such information or prior studies or writings are included or relied upon by the 

document owner, those materials are fully attributed. Mr. LaBone’s Disclosure Statement is available 

at www.oraucoc.org.
Document No. ORAUT-OTIB-0061 Revision No. 00 Effective Date: 06/22/2007 Page 14 of 30

[1] Lochamy, Joseph C. ORAU Team. Senior Health Physicist. February 2007.

PORECON records with “R” (Rejected) entries in the PROBLEM_FLG field were not used 

because they had been flagged as unreliable for some reason. Null entries in the results 

(BQ_DAY) field obviously can not be used, since there are no data to use.

[2] Lochamy, Joseph C. ORAU Team. Senior Health Physicist. February 2007.

PURECON records with nonblank fields for PROBLEM_FLG or DTPA, LNAME=QC, or a blank 

result field were not used because they were unreliable (e.g., nonblank PROBLEM_FLG), not 

representative of normal exposures (e.g., nonblank DPTA entry), a quality control sample 

(e.g., LNAME=QC) or contained no results.

[3] LaBone, Thomas R. ORAU Team. Deputy Principal Internal Dosimetrist. February 2007.

The uniform absolute error of 1 weights all results equally; other fitting schemes weight high 

values or low values disproportionally. Because the median and 84th percentile values were 

determined from statistical analysis of many samples in each interval, there was no a priori

reason to weight results from any one interval over another. Additionally, the polonium results 

were recorded as activity/ml and the statistical analyses were performed in those units. 

However, the IMBA software requires that all excreta data be entered as total excretion per 

day; hence, the statistical parameters were converted to excretion per day before intake 

calculations were made using IMBA. 

[4] LaBone, Thomas R. ORAU Team. Deputy Principal Internal Dosimetrist. February 2007. 

Determinations were made according to ORAUT (2005). The choice of intervals and resulting 

fits were peer reviewed by the Principal Internal Dosimetrist. The breathing rate and particle 

size distribution are project default values to be used unless site-specific information indicates 

otherwise. No information has been found concerning intakes at Mound that shows that the 

default values should not be used. See, for instance, OCAS-IG-002, “Internal Dose 

Reconstruction Implementation Guide,” and ICRP Publication 66, “Human Respiratory Tract 

Model for Radiological Protection.”

[5] LaBone, Thomas R. ORAU Team. Deputy Principal Internal Dosimetrist. February 2007.

Determinations were made according to ORAUT (2005). The choice of intervals and resulting 

fits were peer reviewed by the Principal Internal Dosimetrist. The breathing rate and particle 

size distribution are project default values to be used unless site-specific information indicates 

otherwise. No information has been found concerning intakes at Mound that shows that the 

default values should not be used. See, for instance, OCAS-IG-002, “Internal Dose 

Reconstruction Implementation Guide,” and ICRP Publication 66, “Human Respiratory Tract 

Model for Radiological Protection.”

[6] LaBone, Thomas R. ORAU Team. Deputy Principal Internal Dosimetrist. February 2007.

Determinations were made according to ORAUT (2005). The choice of intervals and resulting 

fits were peer reviewed by the Principal Internal Dosimetrist.

[7] LaBone, Thomas R. ORAU Team. Deputy Principal Internal Dosimetrist. February 2007.

Determinations were made according to ORAUT (2005). The choice of intervals and resulting 

fits were peer reviewed by the Principal Internal Dosimetrist.

[8] Mahathy, Michael and Lochamy, Joseph C. ORAU Team. Coworker Statistics Analyst and 

Senior Health Physicist. February 2007. The table was compiled by Lochamy from data 

generated by Mahathy. 
Document No. ORAUT-OTIB-0061 Revision No. 00 Effective Date: 06/22/2007 Page 15 of 30

[9] LaBone, Thomas R. ORAU Team. Deputy Principal Internal Dosimetrist. February 2007. 

Figures were generated by LaBone from IMBA results.

[10] LaBone, Thomas R. ORAU Team. Deputy Principal Internal Dosimetrist. February 2007. 

Determinations were made according to ORAUT (2005). The choice of intervals and resulting 

fits were peer reviewed by the Principal Internal Dosimetrist. 

[11] LaBone, Thomas R. ORAU Team. Deputy Principal Internal Dosimetrist. February 2007. 

Determinations were made according to ORAUT (2005). The choice of types and applications 

were peer reviewed by the Principal Internal Dosimetrist. 

[12] LaBone, Thomas R. ORAU Team. Deputy Principal Internal Dosimetrist. February 2007. 

Figures were generated by LaBone from IMBA results.

[13] LaBone, Thomas R. ORAU Team. Deputy Principal Internal Dosimetrist. February 2007. 

Determinations were made according to ORAUT (2005). The choice of intervals and resulting 

fits were peer reviewed by the Principal Internal Dosimetrist. Figures were generated by 

LaBone from IMBA results.

[14] LaBone, Thomas R and Lochamy, Joseph C.. ORAU Team. Deputy Principal Internal 

Dosimetrist and Senior Health Physicist. February 2007. Determinations were made by 

Labone according to ORAUT (2005). The tables were compiled by Lochamy from data 

generated by Lochamy. 

[15] LaBone, Thomas R. ORAU Team. Deputy Principal Internal Dosimetrist. February 2007. 

Determinations were made according to ORAUT (2005). The choice of intervals and resulting 

fits were peer reviewed by the Principal Internal Dosimetrist.

[16] LaBone, Thomas R., Mahathy, Michael, and Lochamy, Joseph C. ORAU Team. Deputy 

Principal Internal Dosimetrist, Coworker Statistics Analyst, and Senior Health Physicist. 

February 2007. Determinations were made by LaBone according to ORAUT (2005). The 

table was compiled by Lochamy from data generated by Mahathy.

[17] LaBone, Thomas R. ORAU Team. Deputy Principal Internal Dosimetrist. February 2007. 

Determinations were made according to ORAUT (2005). The choice of intervals and resulting 

fits were peer reviewed by the Principal Internal Dosimetrist. The minimum GSD of 3 is 

established in ORAUT-OTIB-0060, “Internal Dose Reconstruction.” It reflects the overall 

uncertainty associated with biokinetic modeling as well as usual radiochemical analysis, and 

indicates that even though the spread in coworker excreta results for a given population (e.g., 

a year of excreta samples) can have a GSD of <3, the uncertainty of intakes determined using 

the biokinetic models is no less than 3.

[18] LaBone, Thomas R. and Lochamy, Joseph C.. ORAU Team. Deputy Principal Internal 

Dosimetrist and Senior Health Physicist. February 2007. Determinations were made by 

LaBone according to ORAUT (2005). The tables were compiled by Lochamy from data 

generated by Lochamy. 

[19] LaBone, Thomas R and Lochamy, Joseph C.. ORAU Team. Deputy Principal Internal 

Dosimetrist and Senior Health Physicist. February 2007. Determinations were made by 

LaBone according to ORAUT (2005). The tables were compiled by Lochamy from data 

generated by Lochamy. 
Document No. ORAUT-OTIB-0061 Revision No. 00 Effective Date: 06/22/2007 Page 16 of 30

[20] LaBone, Thomas R. and Lochamy, Joseph C. ORAU Team. Deputy Principal Internal 

Dosimetrist and Senior Health Physicist. February 2007. Determinations were made by 

LaBone according to ORAUT (2005) and ORAUT (2004b). The table was compiled by 

Lochamy from ORAUT (2004b).

REFERENCES

ORAUT (Oak Ridge Associated Universities Team), 2004a, Coworker Data Exposure Profile 

Development, ORAUT-PLAN-0014, Rev. 00, Oak Ridge, Tennessee, November 24.

ORAUT (Oak Ridge Associated Universities Team), 2004b, Technical Basis Document for the Mound 

Site – Occupational Internal Dosimetry, ORAUT-TKBS-0016-5, Rev. 00, Oak Ridge, 

Tennessee, September 9.

ORAUT (Oak Ridge Associated Universities Team), 2005, Analysis of Coworker Bioassay Data for 

Internal Dose Assignment, ORAUT-OTIB-0019, Rev. 01, Oak Ridge, Tennessee, October 7.

ORAUT (Oak Ridge Associated Universities Team), 2006, Generating Summary Statistics for 

Coworker Bioassay Data, ORAUT-PROC-0095, Rev. 00, Oak Ridge, Tennessee, June 5.
Document No. ORAUT-OTIB-0061 Revision No. 00 Effective Date: 06/22/2007 Page 17 of 30

Table A-1. 50th- and 84th-percentile urinary excretion rates of 210Po, 1944 to 1957 (Bq/d). 

Effective date 50th percentile 84th percentile Effective date 50th percentile 84th percentile

08/15/1944 8.33E+01 5.07E+02 05/15/1951 1.30E+00 9.08E+00

11/15/1944 8.89E+01 3.56E+02 08/15/1951 1.41E+00 8.73E+00

02/15/1945 1.01E+02 2.97E+02 11/15/1951 1.10E+00 7.89E+00

05/15/1945 1.39E+02 5.13E+02 02/15/1952 1.25E+00 6.68E+00

08/15/1945 5.17E+01 2.03E+02 05/15/1952 9.10E-01 5.33E+00

11/15/1945 5.45E+01 2.27E+02 08/15/1952 7.03E-01 4.84E+00

02/15/1946 4.56E+01 1.99E+02 11/15/1952 1.18E+00 7.19E+00

05/15/1946 8.63E+01 2.92E+02 02/15/1953 1.05E+00 7.53E+00

08/15/1946 2.10E+01 1.04E+02 05/15/1953 9.60E-01 5.68E+00

11/15/1946 1.88E+01 9.53E+01 08/15/1953 1.03E+00 4.51E+00

02/15/1947 9.26E+00 6.78E+01 11/15/1953 4.56E-01 4.09E+00

05/15/1947 1.01E+01 6.84E+01 02/15/1954 7.22E-01 6.44E+00

08/15/1947 1.32E+01 8.68E+01 05/15/1954 1.47E+00 6.37E+00

11/15/1947 2.16E+01 1.10E+02 08/15/1954 3.24E+00 9.88E+00

02/15/1948 3.18E+01 1.71E+02 11/15/1954 1.41E+00 8.96E+00

05/15/1948 2.62E+01 1.36E+02 02/15/1955 1.62E+00 5.72E+00

08/15/1948 1.52E+01 8.99E+01 05/15/1955 5.26E-01 2.62E+00

11/15/1948 1.90E+01 1.23E+02 08/15/1955 5.54E-01 3.90E+00

02/15/1949 7.12E+00 7.36E+01 11/15/1955 9.41E-01 1.26E+01

05/15/1949 2.88E+00 2.27E+01 02/15/1956 4.31E-01 7.80E+00

08/15/1949 2.77E+00 2.02E+01 05/15/1956 8.55E-01 5.51E+00

11/15/1949 2.29E+00 2.00E+01 08/15/1956 1.78E-01 2.44E+00

02/15/1950 1.43E+00 1.39E+01 11/15/1956 6.41E-02 3.01E+00

05/15/1950 7.55E-01 8.97E+00 02/15/1957 2.98E-01 6.07E+00

08/15/1950 7.96E-01 7.03E+00 05/15/1957 4.53E-02 2.09E+00

11/15/1950 6.05E-01 8.06E+00 08/15/1957 4.34E-01 3.23E+00

02/15/1951 1.02E+00 7.32E+00 11/15/1957 6.68E-01 6.92E+00

ATTACHMENT A

COWORKER DATA TABLES

Page 1 of 4
Document No. ORAUT-OTIB-0061 Revision No. 00 Effective Date: 06/22/2007 Page 18 of 30

Table A-2. 50th- and 84th-percentile urinary excretion rates of 210Po, 1958 to 1973 (Bq/d). 

Effective date 50th percentile 84th percentile Effective date 50th percentile 84th percentile

02/15/1958 9.75E-01 6.67E+00 11/15/1964 4.35E-02 2.00E-01

05/15/1958 1.00E+00 1.20E+01 02/15/1965 3.60E-02 1.33E-01

08/15/1958 6.22E-01 9.34E+00 05/15/1965 1.90E-02 6.91E-02

11/15/1958 6.82E-01 8.50E+00 08/15/1965 3.27E-02 1.07E-01

02/15/1959 1.37E+00 1.28E+01 11/15/1965 1.34E-02 7.85E-02

05/15/1959 1.32E+00 7.19E+00 02/15/1966 8.63E-03 4.57E-02

08/15/1959 9.35E-01 7.44E+00 05/15/1966 1.12E-02 5.53E-02

11/15/1959 1.32E+00 1.08E+01 08/15/1966 1.53E-02 9.59E-02

02/15/1960 6.88E-01 6.49E+00 11/15/1966 1.77E-02 8.22E-02

05/15/1960 4.01E-01 4.16E+00 02/15/1967 2.11E-02 7.49E-02

08/15/1960 5.34E-01 4.58E+00 05/15/1967 9.13E-03 4.15E-02

11/15/1960 5.92E-01 4.91E+00 08/15/1967 2.00E-03 2.33E-02

02/15/1961 6.98E-01 6.04E+00 11/15/1967 7.77E-04 2.24E-02

05/15/1961 5.02E-01 3.75E+00 02/15/1968 4.09E-03 5.91E-02

08/15/1961 4.12E-01 2.57E+00 05/15/1968 1.30E-02 9.17E-02

11/15/1961 2.89E-01 2.33E+00 08/15/1968 2.19E-03 1.24E-01

02/15/1962 2.51E-01 1.42E+00 11/15/1968 7.16E-03 9.72E-02

05/15/1962 3.46E-01 1.98E+00 02/15/1969 1.87E-03 2.55E-02

08/15/1962 4.88E-01 2.63E+00 05/15/1969 5.10E-03 2.35E-02

11/15/1962 1.85E-01 1.80E+00 08/15/1969 1.14E-03 1.15E-02

02/15/1963 2.09E-01 1.57E+00 11/15/1969 3.99E-05 1.58E-03

05/15/1963 9.66E-02 7.90E-01 02/15/1970 1.45E-03 9.66E-03

08/15/1963 9.01E-02 5.51E-01 05/15/1970 1.37E-02 4.73E-02

11/15/1963 3.38E-01 1.66E+00 11/15/1970 2.20E-02 6.67E-02

02/15/1964 4.71E-02 2.68E-01 07/01/1971 5.96E-04 1.52E-02

05/15/1964 1.86E-02 1.56E-01 07/01/1972 1.06E-02 2.40E-01

08/15/1964 4.43E-02 2.03E-01 07/01/1973 4.38E-03 4.61E-01

Table A-3. Type M 210Po intake rates (Bq/d) and dates. 

Start date End date 50th percentile 84th percentile GSD

07/01/1944 03/31/1946 4097.6 15796 3.9

04/01/1946 03/31/1949 800.19 4602.3 5.8

04/01/1949 03/31/1960 39.851 320.28 8.0

04/01/1960 03/31/1965 5.7883 36.121 6.2

04/01/1965 12/31/1973 0.34853 3.0638 8.8

Table A-4. Type F 210Po intake rates (Bq/d) and dates. 

Start date End date 50th percentile 84th percentile GSD

07/01/1944 03/31/1946 1189.5 4628 3.89

04/01/1946 03/31/1949 254.96 1416.8 5.56

04/01/1949 03/31/1960 12.192 97.456 7.99

04/01/1960 03/31/1965 2.0696 13.856 6.70

04/01/1965 12/31/1973 0.10303 0.91451 8.88

ATTACHMENT A

COWORKER DATA TABLES

Page 2 of 4

ATTACHMENT A

COWORKER DATA TABLES

Page 2 of 4
Document No. ORAUT-OTIB-0061 Revision No. 00 Effective Date: 06/22/2007 Page 19 of 30

ATTACHMENT A 

COWORKER DATA TABLES

Page 3 of 4

Table A-5. 50th- and 84th-percentile urinary excretion rates of total plutonium, 1956 to 1975 (pCi/d). 

Effective date 50th percentile 84th percentile Effective date 50th percentile 84th percentile

07/01/1956 1.88E+00 4.49E+00 02/15/1968 5.01E-02 2.17E-01

07/01/1957 2.26E+00 4.03E+00 05/15/1968 7.91E-02 2.70E-01

07/01/1958 1.14E+00 2.00E+00 08/15/1968 6.23E-02 2.26E-01

07/01/1959 1.53E+00 2.73E+00 11/15/1968 4.47E-02 2.67E-01

07/01/1960 1.72E+00 9.81E+00 02/15/1969 5.42E-02 4.69E-01

07/01/1961 8.01E-02 6.50E-01 05/15/1969 5.14E-02 3.87E-01

02/15/1962 3.49E-02 2.25E-01 08/15/1969 8.76E-02 8.74E-01

05/15/1962 7.15E-02 4.42E-01 11/15/1969 4.45E-02 2.63E-01

08/15/1962 1.01E-01 3.63E-01 02/15/1970 2.42E-02 1.47E-01

11/15/1962 1.06E-01 4.27E-01 05/15/1970 3.27E-02 1.75E-01

02/15/1963 5.31E-02 2.88E-01 08/15/1970 2.93E-02 1.31E-01

05/15/1963 7.53E-02 5.73E-01 11/15/1970 1.98E-02 9.93E-02

08/15/1963 5.19E-02 3.41E-01 02/15/1971 2.90E-02 1.64E-01

11/15/1963 7.01E-02 3.65E-01 05/15/1971 2.03E-02 1.16E-01

02/15/1964 8.98E-02 3.53E-01 08/15/1971 2.21E-02 1.15E-01

05/15/1964 1.19E-01 3.64E-01 11/15/1971 2.77E-02 1.46E-01

08/15/1964 1.18E-01 3.62E-01 02/15/1972 2.83E-02 1.62E-01

11/15/1964 1.59E-01 6.00E-01 05/15/1972 2.01E-02 1.15E-01

02/15/1965 1.03E-01 5.95E-01 08/15/1972 2.05E-02 1.21E-01

05/15/1965 1.07E-01 5.11E-01 11/15/1972 2.21E-02 1.27E-01

08/15/1965 1.07E-01 5.58E-01 02/15/1973 3.80E-02 1.80E-01

11/15/1965 5.56E-02 2.62E-01 05/15/1973 3.32E-02 1.40E-01

02/15/1966 9.62E-02 3.70E-01 08/15/1973 2.29E-02 1.08E-01

05/15/1966 7.11E-02 2.94E-01 11/15/1973 1.21E-02 8.04E-02

08/15/1966 7.09E-02 2.29E-01 02/15/1974 3.65E-02 1.41E-01

11/15/1966 8.56E-02 2.87E-01 05/15/1974 4.34E-02 1.91E-01

02/15/1967 7.68E-02 2.87E-01 08/15/1974 3.70E-02 1.83E-01

05/15/1967 8.63E-02 3.37E-01 11/15/1974 4.74E-02 2.06E-01

08/15/1967 7.38E-02 2.91E-01 02/15/1975 1.10E-02 7.75E-02

11/15/1967 4.86E-02 2.27E-01 05/15/1975 1.13E-02 9.84E-02
Document No. ORAUT-OTIB-0061 Revision No. 00 Effective Date: 06/22/2007 Page 20 of 30

Table A-6. 50th- and 84th-percentile urinary excretion rates of total plutonium, 1975 to 1990 (pCi/d). 

Effective date 50th percentile 84th percentile Effective date 50th percentile 84th percentile

08/15/1975 3.49E-02 1.69E-01 05/15/1983 1.24E-02 7.51E-02

11/15/1975 1.71E-02 8.51E-02 08/15/1983 1.08E-02 6.97E-02

02/15/1976 3.49E-02 1.66E-01 11/15/1983 7.71E-03 5.37E-02

05/15/1976 1.19E-02 7.15E-02 02/15/1984 9.94E-03 5.88E-02

08/15/1976 1.46E-02 6.91E-02 05/15/1984 1.22E-02 6.80E-02

11/15/1976 1.80E-02 8.28E-02 08/15/1984 7.50E-03 4.01E-02

02/15/1977 2.13E-02 9.59E-02 11/15/1984 8.39E-03 4.20E-02

05/15/1977 2.13E-02 9.50E-02 02/15/1985 2.49E-03 2.29E-02

08/15/1977 1.15E-02 7.02E-02 05/15/1985 3.05E-03 2.84E-02

11/15/1977 1.56E-02 8.01E-02 08/15/1985 1.12E-03 1.44E-02

02/15/1978 7.79E-03 4.92E-02 11/15/1985 1.28E-03 1.51E-02

05/15/1978 4.68E-03 4.20E-02 02/15/1986 2.25E-03 2.05E-02

08/15/1978 4.44E-03 2.99E-02 05/15/1986 3.86E-03 3.76E-02

11/15/1978 8.12E-03 6.62E-02 08/15/1986 3.09E-03 2.71E-02

02/15/1979 2.78E-03 2.96E-02 11/15/1986 4.11E-03 3.44E-02

05/15/1979 6.74E-03 5.00E-02 02/15/1987 6.20E-03 3.27E-02

08/15/1979 1.80E-02 7.82E-02 05/15/1987 6.85E-03 4.20E-02

11/15/1979 7.70E-03 6.01E-02 08/15/1987 4.05E-03 2.85E-02

02/15/1980 6.84E-03 4.16E-02 11/15/1987 4.61E-03 3.01E-02

05/15/1980 1.77E-02 9.15E-02 02/15/1988 5.23E-03 3.55E-02

08/15/1980 1.80E-02 7.22E-02 05/15/1988 5.50E-03 3.60E-02

11/15/1980 2.41E-02 1.33E-01 08/15/1988 3.47E-03 2.52E-02

02/15/1981 2.22E-02 1.06E-01 11/15/1988 2.65E-03 3.32E-02

05/15/1981 2.63E-02 8.57E-02 02/15/1989 3.17E-03 3.06E-02

08/15/1981 2.02E-02 9.85E-02 05/15/1989 3.90E-03 3.11E-02

11/15/1981 2.17E-02 1.17E-01 08/15/1989 1.88E-03 1.83E-02

02/15/1982 1.89E-02 9.22E-02 11/15/1989 1.23E-03 1.66E-02

05/15/1982 9.69E-03 5.85E-02 02/15/1990 1.16E-03 1.52E-02

08/15/1982 1.23E-02 7.39E-02 05/15/1990 1.27E-03 1.40E-02

11/15/1982 2.97E-02 9.91E-02 08/15/1990 6.78E-04 1.07E-02

02/15/1983 1.24E-02 6.12E-02 11/15/1990 1.83E-03 1.18E-02

Table A-7. Type M plutonium intake rates (pCi/d) and dates. 

Start date End date 50th percentile 84th percentile GSD

01/01/1956 12/31/1957 750.98 1,073.4 1.43a

01/01/1958 12/31/1960 436.49 1,073.4 2.46a

01/01/1961 12/31/1967 12.141 65.823 5.42

01/01/1968 12/31/1969 12.141 141.98 11.69

01/01/1970 12/31/1977 2.2361 20.445 9.14

01/01/1978 12/31/1984 2.2361 13.013 5.82

01/01/1985 12/31/1990 0.59706 4.872 8.16

a. Actual. Adjust all GSD <3 to 3 for dose calculations.

Table A-8. Type S plutonium intake (pCi/d) rates and dates. 

Start date End date 50th percentile 84th percentile GSD

01/01/1956 12/31/1990 0.54041 8.4956 3.89

ATTACHMENT A

COWORKER DATA TABLES

Page 4 of 4
Document No. ORAUT-OTIB-0061 Revision No. 00 Effective Date: 06/22/2007 Page 21 of 30

Figure B-1. Predicted (line) and observed (dots) 50th-percentile urinary excretion 

assuming inhalation intakes of type M 210Po. 

Figure B-2. Predicted (line) and observed (dots) 84th-percentile urinary excretion 

assuming inhalation intakes of type M 210Po. 

ATTACHMENT B

COWORKER DATA FIGURES

Page 1 of 10
Document No. ORAUT-OTIB-0061 Revision No. 00 Effective Date: 06/22/2007 Page 22 of 30

Figure B-3. Predicted (line) and observed (dots) 50th-percentile urinary excretion 

assuming inhalation intakes of type F 210Po. 

Figure B-4. Predicted (line) and observed (dots) 84th-percentile urinary excretion 

assuming inhalation intakes of type F 210Po. 

ATTACHMENT B

COWORKER DATA FIGURES

Page 2 of 10
Document No. ORAUT-OTIB-0061 Revision No. 00 Effective Date: 06/22/2007 Page 23 of 30

Figure B-5. Predicted (line) and observed (dots) 50th-percentile urinary excretion 

assuming inhalation intakes of type M plutonium, 1956 to 1957. 

Figure B-6. Predicted (line) and observed (dots) 50th-percentile urinary excretion 

assuming inhalation intakes of type M plutonium, 1958 to 1960. 

ATTACHMENT B

COWORKER DATA FIGURES

Page 3 of 10
Document No. ORAUT-OTIB-0061 Revision No. 00 Effective Date: 06/22/2007 Page 24 of 30

Figure B-7. Predicted (line) and observed (dots) 50th-percentile urinary excretion 

assuming inhalation intakes of type M plutonium, 1961 to 1969. 

Figure B-8. Predicted (line) and observed (dots) 50th-percentile urinary excretion 

assuming inhalation intakes of type M plutonium, 1970 to 1984. 

ATTACHMENT B

COWORKER DATA FIGURES

Page 4 of 10
Document No. ORAUT-OTIB-0061 Revision No. 00 Effective Date: 06/22/2007 Page 25 of 30

Figure B-9. Predicted (line) and observed (dots) 50th-percentile urinary excretion 

assuming inhalation intakes of type M plutonium, 1985 to 1990. 

Figure B-10. Predicted (line) and observed (dots) 50th-percentile urinary excretion 

assuming inhalation intakes of type M plutonium, 1956 to 1990. 

ATTACHMENT B

COWORKER DATA FIGURES

Page 5 of 10
Document No. ORAUT-OTIB-0061 Revision No. 00 Effective Date: 06/22/2007 Page 26 of 30

Figure B-11. Predicted (line) and observed (dots) 84th-percentile urinary excretion 

assuming inhalation intakes of type M plutonium, 1956 to 1960. 

Figure B-12. Predicted (line) and observed (dots) 84th-percentile urinary excretion 

assuming inhalation intakes of type M plutonium, 1961 to 1967. 

ATTACHMENT B

COWORKER DATA FIGURES

Page 6 of 10
Document No. ORAUT-OTIB-0061 Revision No. 00 Effective Date: 06/22/2007 Page 27 of 30

Figure B-13. Predicted (line) and observed (dots) 84th-percentile urinary excretion 

assuming inhalation intakes of type M plutonium, 1968 to 1969. 

Figure B-14. Predicted (line) and observed (dots) 84th-percentile urinary excretion 

assuming inhalation intakes of type M plutonium, 1970 to 1977. 

ATTACHMENT B

COWORKER DATA FIGURES

Page 7 of 10
Document No. ORAUT-OTIB-0061 Revision No. 00 Effective Date: 06/22/2007 Page 28 of 30

Figure B-15. Predicted (line) and observed (dots) 84th-percentile urinary excretion 

assuming inhalation intakes of type M plutonium, 1978 to 1984. 

Figure B-16. Predicted (line) and observed (dots) 84th-percentile urinary excretion 

assuming inhalation intakes of type M plutonium, 1985 to 1990. 

ATTACHMENT B

COWORKER DATA FIGURES

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Document No. ORAUT-OTIB-0061 Revision No. 00 Effective Date: 06/22/2007 Page 29 of 30

Figure B-17. Predicted (line) and observed (dots) 84th-percentile urinary excretion 

assuming inhalation intakes of type M plutonium, 1956 to 1990. 

Figure B-18. Predicted (line) and observed (dots) 50th-percentile urinary excretion 

assuming a single chronic inhalation intake of type S plutonium, 1956 to 1990. 

ATTACHMENT B

COWORKER DATA FIGURES

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Document No. ORAUT-OTIB-0061 Revision No. 00 Effective Date: 06/22/2007 Page 30 of 30

Figure B-19. Predicted (line) and observed (dots) 84th-percentile urinary excretion 

assuming a single chronic inhalation intake of type S plutonium, 1956 to 1990. 

ATTACHMENT B

COWORKER DATA FIGURES

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